ML20070S139

From kanterella
Jump to navigation Jump to search
Forwards Contentions Discussed During Exit Interview Re Written Exam Administered to Senior Operator,D Krause on 910225
ML20070S139
Person / Time
Site: University of Virginia
Issue date: 02/26/1991
From: Farrar J
VIRGINIA, UNIV. OF, CHARLOTTESVILLE, VA
To: David Silk
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20070S101 List:
References
NUDOCS 9104020157
Download: ML20070S139 (50)
v • d • e


Text

-

ENCLO9URE 2 4

\\CllHOi. Of ENGINEERING @

& APPLIED SCIENCE

(){1%lRItilh1OF AUCIMM f. Mils!LRIVG

& l. ngl \\f.l. RING Pin SICS t

Umveruly of Virpnia l

Reactor Facility 1

Charlottewille, VA 2290b2442 804 924 7136 FAX 804 982 2634 February 26, 1991 Mr David Silk USRNC Region I 475 Allendale Road Kin 6 of Prussia, PA 19406

Dear Mr. Silk,

As we discussed in your exit interview, we have the following contentions regarding the written examination for Senior Operator administered to Mr, Donald Krause on February 25, 1991,

1) Question A 018 concerning sub critical measurements to predict number of fuel elements, Detector A predicts - 55 elements but Detector B predicts 45 elements. We feel you should use the more conservative of the two, therefore the answer should be 45 (a),

l

2) Question A 019 concerning regulating rod _ movement to compensate for temperature increase, For a temperature increase of 10 'F the reactivity increase would be 2 E 3.

The average differential worth of che regulating rod is - 2 E 4, therefore the rod would have to move 10 inches, The correct answer should be (d),

3) Question C 001 concerning a standard fuel element.

There are two types of fuel described in the SAR, a standard element with 12 flat plates or a standard element with 18 curved plates.

Either (a) or (d) is a correct answer.

4) Question C-006 concerning the instrumentation that utilizes a compensated ion chamber.

Both the Intermediate range and Linear range utilize this type of detector, therefore either (b) or (d) would be correct,

5) Question C 018 concerning the internal pressures required to break l

the reactor room integrity.

When I first looked at the question I agreed with the NRC answer of (b).223 psig, but on further analysis I must disagree.

If there is a 6" water seal the pressure must force the water down 6" on the reactor room side but push the water up 12" on the outside, therefore the correct answer should be (d).443 psig.

9104020157 910325 PDR ADOCK 05000062 V

PDR

l "I"*

If I Can Provide further elarift a o p ease c 1 m,

Sincerely, Q.

v (LH.0A-JVP. Farrar, Administrate -

U,Va,-Reactor Facility ec: D.R. Krause R.U Mulder 6

a 5

...w..

ATTACHMENT 3 NRC RESOLUTIONS TO FACILITY WRITTEN EXAMINATION COMMENTS fKtestion R Resobition A.i8 Due to a math-error. in performing a i/M plot, the NRC will accept "a" as the correct response instead of "c."

A.i9 Due to a math error in calcula t

,*g rod position, the NRC will accept "d" as the corretc response instead of "c."

C.0i Based upon facility reference material supporting two answers, the NRC will accept either "a" or - "d " as the correct responses.

C.06 The facility reference material does support "d"

as another correct response.

The NRC will accept either "b"

or "d"

as correct responses.

C.iB Due to a ma th error in cr.lculating dif f erential pressure 3 the.NRC will accept "d"

instead of'"b" as the correct

response, i

i 4

m u.

.i.,,,, _ -i-ium i i i

Jl

-gs.501 1

Rev 6 06/01/90 4

ES-501-4 CONTRACT EXAMINER EVALUATION 1.

Examination Information:

Facility UA.v. N h_g AL.

Examination Type bf ace md I

Exam Date(s) c'/n-at/m

  1. of Candidates

-O R0s

/ SR0s Date Written Examination Received by Regional Reviewer-2 /7M /

Date Simulator Scenarios Received-by Regional Reviewer WA Date All Graded Examinations Received by Region MN 2.

Examiner Information:

NAME CONTRACTOR LEVEL OF EFFORT h,-:c s 0<nieh Suhs h pk SRC 3.

Evaluation:

For each activity-listed below indicate whether the contractor's performance was in compliance with the appropriate sections.

of the Examiner's Standards (Yes/No).

Use N/A when warranted. ' Justify all responses of "No" in the comments section.

Negative comments should include the deficiency and the associated ' requirement (Examiner Standard, NUREG/BR-0122, etc.) that the contractor failed to meet.

WRITTEN SIMULATOR.

JPMs/

ACTIVITY EXAM SCENARIOS-WALKTHROUGH Write and-Prepare'

\\/e9

'Vd NN On Site Preparation

  1. 4 I

Administer M

Grade / Document

[4 Review /QA

\\/c 5 I

N

-/

Examiner Standards 9 of 18

..-.....m__._---------

-. - ^ - - "

E5-501 Rev 6 06/01/90 4.

Audit of Examiners:

List of examiners that were audited and whether or not they conformed with guidance in the Examiner Standards for the areas evaluated during the audit.

Attach a copy of the Form 308.

Denots the reasons for any negative ratings in the comment section Delow or on the form 308.

All negative comments should refer to pertinent guidance fof-j examination administration.

1 SIMULATOR WALKTHROUGH NAME ES CONFORMANCE ES CONFORMANCE TYPE OF CANDIDATE N

S.

Comments:

Attach additional sheets as necessary, Em

~m J,w + ie l /l v,..h.u H ) an

d., !,

.m. - n e a..

C.n J:,

.ve, c e

a

,,a:n nn.de f,

e,.,_ %m r y, an ). L J,,,,

t,e J

,e,,,,,,,)

b.. J c J!.

,n e;. r.,,.,,,.. ous<.d u.. //, s.wegeni -o;-ers /: -e c'

v., 'k' ]

Ac wf.]el veII:n.., k l. 4, A c l L, o rie k.,, ) J h.,

n t

s

'an c.t/ f t en $ w t e t, hg A t (if V v.

n *1 4 'sV t f 6 n

p, ar_

( k-s sm

  • t,y 1

o

+ u e '. ou.m U s 4 c.,,, t,l. cid e ),

S.tlb.., a,.) m w kev celln+

0 er ec,.,

a, e -~ r e i c ~ p?n en enar ab,r; %l h.

NRC.

pc

% ~ < < <h.,. + / a e ks

., ~,e r ; r.l,lo n c.ce 4, a wa.

a.,

4, hall a c e u,de s ) w h,l wie lx ao was o.

v 1

Form Completed By:

hivQ'l -

0 47/'//

Date Chief Ext.niner:

hrMI kl7/"tr Date Section Chief:

Y_.7 s_ ol.

3 /,< 7/9 -

O Date l

Examiner Standards 10 of 18 l

ENCLOSURE 3 I

U.

S.

NUCLEAR REGULi70kY COMMh 110N NON-PCb'ER REACTOR LICENSE EXAMINn / ION FACILITY:

Univ. of Viroinig I

REACTOR TYPE:

Test i

DATE ADMINISTERED:

91/02/25 REGION:

d s

CANDIDATE:

1 i

Jf3TRQCTIONS TO CANDIDATE:

Answers are to be written on the exam page itself, or the answer sheet l

irovided.

Write answers one side ONLY.

. Attach any answer sheets to the examination.

Point' for each question are indicated in parentheses for each question.: A 70% in each section is required to pass the examination.

Examinations will be picked up three (3) hours after the examination starts.

% OF CATEGORY

% OF CANDIDATE'S CATEGORY VALUE TOTAL SCORE VALUE CATEGORY 19.00 31.67 A.

REACTOR THEORY. THERMO.DYNAMIOG AND FACILITY OPERATING CHARACTERISTICS 21.00 35.00 B.

NORMAL AND EMERGENCY OPERAT1NG PROCEDURES AND RADIOLOGICAL CONTROLS 20.00 33.33 C.

PLANT AND RADIATION MONITORING SYSTEMS 60.00 TOTALS FINAL GRADE All work done on this c>nmination is my own.

I have neither given nor received aid.

(

Candidale's Signature

._s 4

NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During the administration of this examination the following rules apply:

1.

Cheatint the examination means an automatic denial of your' application-f on and could result in more severe penalties.

2. After the examination has been completed, you must sign the statement on the cover shoot ind i c a tinc. that the work is your own and you have not received or given a sistance in completing the examination.

This must he done after you complete the examination, i

3. Restroom trip 5 are to be limited and only one candidate at a time may leave.

You must avoid all contac ts with anyone outside the examination room to avoid even the appearance or possibility of c hea t ina...

w. (Jse black int or dark pencil only to facilitate legible reproductions.

S. Print your namo in the blank provided-in the upper right-hand corner of the examination cover shoot.

6. Fill in the date on the cover sheet of the eHamination (if necessary).

~7. You may write your answers on the examination question pace or on a separate sheet of paper.

USE ONLY THE PAPER PROVIDED AND DO NOT WRITli GN THE DACK SIDE OF THE PAGE.

8. If you write your answers on the examination question page and you need more space to enswer a specific question, use a separate sheet of-'the paper provided and insert 1-t directly after the specific question.

DO NOT WRITE ON THE DACK SIDE OF THE EXAMINATION QUESTION PAGE.

9. P r in t yo.u r name in the upper right-hand corner of the.first-page of each section of your answer sheets whether you use the examination question a

pages or separate sheets of paper.

Initial each page.

10. Before you turn in your examination, consecutively number-each answer sheet, including any addilianal pages inserted when writing your an?wers on the enaminatiori question page.
11. If you are using separate cheets, number each answer as to category and number (i.e. Plant Systems W 04, EPE # 10) and skip at least 3 lines hotween artswers to allow space for grading.

D

12. Write "End of Category" at the end of your answers to a category.

C.

Start eeth category on a new page.

14 Wrtto "l.ast Page" on 'he last answer shoot.

tS. Use nbtmeviations unis if they are commonly used in facility literature.

Avoid using 2ymbols nucn as or stqns 1o avoid a simple transposi. tion error cerulting in an i ntc.rrec t anywer, Write it out.

I d

l 1

mW

- _ _ - _ - - - - _ _ - 'l

16. The point value for eoch quettion in indicated in par enthesen af ter the question.

The amount of blank _ space on an examinatfori question page NOT :n indic ation of is the depth of answer required.

17 Enow all calculations. mtethods, or aut'umptionu used to obtain an answer.

10. Partial credit may be give-Theretire. ANSWER ALL PARTS OF-THE QUESTION AND DO NOT LEAVE ANy ANSWER BLANK.

NOTE: partial credit will NOT be given on multiple choice questions.

19. Pror)rtional grading will be applied.

Any edditionhl wrong informetion that iu provided may count against vou. - For enemple if a question is i

worth one point and cul s for tour responses.

9ech of evhich is worth 0.25 pointu, and you give five responses, vech of your responses will be worth 0.20 points.

If one of your five recpanses le incorrect. O.20 will be deducteu ond your tota l crFJit for that question will be 9.00 1astead of 1.00 oven thoi,

you got the four correct anuwers.

20, if the intent

,f a quehtion is unclear, aul questions of the examiner only.

21. When turning in your examtnetion, assemble the completed examination with ur+ min #+1on questions, entamination aids cne answer sheets.

In addition, turn an all scrap paper.

22. To pass the examination, you must achieve at least 70Y. in each category.
23. There is a time limit of (3) hours for completion of the examination.

(or some other time if itse than the full enamination is taken.)

24. When you are done and have turned in your examination, leave the.examin-ation area os defined by the examiner.

If you are found in this area while the examination is still in progress, your license may be denied or revoked.

a n

I I

l l

EQUATION SilEET

{

f = ma A = AN w = mg A = A e***

n v= s/t A = In2/t 3 0.693/t

=

g a=Vt + ) att o

I I,e-Is i

a=

(Vt V )/t 1 = t.e***

o V

  • V

+ at I =

10 * " / "'

I t

o E = met TVL ' 1.3/s l

KE = 1 mv2 ilVL = -0. 69 3 /g PE = mgh SCR = S/(1 - Kett )

i w = 0/t C R, = S/(1 K, t t s )

W=

v AP CH (1 - K,tti)

CR (1 2

Ker ra )

i

=

2

CR /CRo (IID )/4 M

1/(1 A=

Kett) i AE = 931 om M= (1-K rto)/(1 - Ketti) f e

in = V, yap SDM = (1 K

I/Keff

(

ett Q = 6C At l'

=

p 10*4 seconds 6 = UAat I = 0.1 seconds *1 Pwr = Wr h Id a

Ind:

=

t t P = P 108"( t )

Igd 2 = Inda!

3 P = P e'/7 R/hr = (0.5 CE)/d2 o

(meters) t SUR = 26.06/T R/hr = 6 CE/d2 (reet3 SUR = 26g/f* + ( 0 p )T T=

(f*/p) +

l(0 - #)/5p]

T=

f/(w - 0)

T=

(0 - 9)/(59)

(K,tt **)/Kett = dKett /K rt I

  1. =

r

@= l(f*/(T K,tt il + (dett /(1 + IT))

8 P=

(Sov)/(3 x 10 0)

E=6N Cycle efficiency = (Net work out)/(Energy in)

I

(

Water Parftmeters Mi scellaneous Conve rsiorm 1 gal.

8.345 lbm.

1 Curie =

=

3.7 x 1010 dps 1 gal.

= 3.78 liters i kg

= 2.21 lbm 3

1 ft

= 7.48 gal.

I hp = 2.54 x 10' Btu /hr Density

= 02.4 lbm/ft1 1 mw = 3.11 106 btu /hr s

Density a

= 1 gm/cm 1 in = 2.54 cm Heat of vaporization 970 Btu /lbm

'F 9/5'c + 32

=

=

Heat of fusion

-144 Blu/lbm 5 / 91 ' i' - 32) t

=

1

.\\ t m =

11.7 psi

= 29.9 in Hg.

1 Utu =

778 ft-lbf

  • 1 ft. Hao = 0.1335 lbf/in.

, _ _ _ -. ~.

i 5

10 15 20 25 30 35 40 45 50 55 1.0 1.0 0.9 0.9 0.8 0.8 0.7 0.7 0.6 0.6 1/M 0.5 0.5 0.4 0.4 0.3 0.3 0.2 0.2 0.1 0.1 0.0 0.0 5

10 15 20 25 30 35 40 45 50 55 NUMBER OF BUNDLES INSTALLED Figure 1 1

l

,y -

i; 's

A.

RX THEORY, THERMO F FAC OP CHARC Page 4

I OUESTION: 001 (1.00)

Which one of the following is the definition of the diffusion lenpth of a neutron?

e.

The dis,tence a neutron travels from birth to thermali:ation b.

The distance e neutron travels from birth to absorption L.

The distance a neutron travels from thermali:ation to absorption d.

The distance a neutror: travelc from thermal 1:ation to fission OUESTION: 000 (1.00)

Which one of the following statements describes how Samarium reactivity is offacted by power level?

3.

The EQUILIBRIUM (at power) value of Samarium is DEPENDENT upon power level.

The PEAK valuu of Samarium following a shutdown is DEFENDENT upon power level prior to shutdown b.

The EQUILIBRIUM (at power) value of Samar1un as DEPENDENT upon power Icvel.

The PEAK value of Samarium following a shutdown in INDEPENDENT of power level prior to shutdown.

c.

The EQUILIBRIUM (at power) value of Samarium is INDEPENDENT of power level.

The PEAK value of Samarium following a shutdown is DEPENDENT upon power level prior to shutdown, d.

The EQUILIBRIUM (at power) value of Sa-arium is INDEPENDENT of-power level.

The PEAK value of Sacnarium f ollowing a shutdown in INDEFENDENT of power level prior to shutdown.

(tt$4* CATEDORY A CON 11NUED ON NEXT PAGE 44**f) l

?

t A.

Fyy THEORYuT11Gfit1QJ FAC Q[LG1!6[iE Fage S

h DUESTIONt 003 (1.00)

The reector is cuberitical with a Ke11 of 0.8 and en equilibrium count rete of 20 cpu.

Enough positive reactivity is added to increase the equilibrium I

count rato to 40 cpc with the reactor still subtritical.

The same amount of i

reactivity is again added to core. Which of the following in the condition of the core after the second reactivity addition?

I a.

Subtrilacel wath e count rete of 60 cps

{

b.

Subtri tical with a count rate of 00 cpe I

r c.

Juct critical r

r d.

'3u pe r c ri t i c a l with count. rate increasing l

t

?

DUESTION: 004 (1.00)

Whic h one of the following sources ore used in the UVAR7 E

l a.

Polonium - Plutonium (Po-Pu) b.

Antimony - Beryllium (Sb-De) 5 c.

Antimony - Plutonium (Sb-Pu)

I r

f d.

Polonium -Deryllium (Po-Be) i OUESTION: OOS (1.00)

Which of the following statements describes the concentration of Xenon in the core after a scram from extended operation at 2 MW7

.4.

Xenon concentration initially decreates due to the loss of Iodine production then increases to maximum I

concentration b.

Xenon concentration decreases to a Xenon free condition in approximately ten (10) hours j

c.

Xenon concentration increases to maximum in appronimately ten (10) hours d ae to the reduction in the Xenon burnup term d.

Xenon concentration rcmains at equilibrium value since the production and burnup term of Xenon hos ceased i

(t***t CATEGOW 4 CUN11NUED ON NEXT PAGE 44444)

....-m.o

,.,._..,w,,%,,..yy.

,,...y

._~,_..,,.-.y

A.

RX THEORY, THERMO & FAC OP CHARS Page 6

OUESTION: 006 (1.00)

Which of the following eaustions represents the total neutron production rate for a subcritical reactor?

a.

S-1/L b.

K-1/S c.

5/1-L d.

1-V/S OUESTION: 007 (1.00) 4 Which of the terms below is defined by the following equation?

number of neutrons absorbed in the fuel number of neutrons ebsorbed in the fuel + number of neutrono absorbed in the moderator?

Resonance Escape Probability a.

b.

Geometric Duckling c.

Fant Fission Factor d.

Thermal Utilization Factor t

(t4+t4 CAILGORY A CONTINUED ON NEAI PAGE 4*f4*1 l

4 1

A.

RX 1HEORY. THERMO & FAC OP CHARS Pego 7

1 QUESTION: 000 (1.00)

The reactor has been shutdown from extendeo operation at 2 MW.

Five hourc 1

later the reactor is started up and returned _to 2 MW. Which one of tho-following describes tho automatic regulating rod movement for the following twc hours,?

a.

The regulating rod withdraws as xenon increacet to equilibrium value b.

The regulating rod innerto as Xonon burns out to equalibrium level t.

The regulating rod inserts initially as Xonon burns out, then withdraws as Xenon increases to equilibrium value-d.

The regulating rod withdraws initially au Xenon builds in, then inserts as burnout increases QUESTION: 009

(.l.00)

Which of the following is e correct statement concerning Doppler Broedening?

a.

Neutron absorption by the target is dependent on the temperature of the target and independent of the neutron energy b.

An increase in the target temperature results in thermal onpansion that increases the space between the target atoma. causing a umoller target area for neutrons An increaue'in the target temperature resul'tc in an increase-in the vibration of target atoma-causing the target atoms to appear larger to incoming neutrons d.

Neutron absorption by the target is-dependent on the temperature of the target and independent-of the-isotopic matoup of the target i

I 8

(**11t CATEGORY A CONTINUED ON NEXT PAGE'ttt*t) --

A.

RX THEORY. THERMO & FAC OP CHARS Page e

OUESTION: 010 (1.00)

Select the reason that delayed neutrons allow control of reactor power.

a.

Delayed neutrons decrease the averoge period for a reactivity addition because they thermali::e more quici:ly than prompt ntnitrony, b.

Delayed neuttont cause the leng th of thu evert >ge neutron genetotion time to increewe c.

Delayed neutrons mal e up a larger f rac tion of the flusion neutrons then do the pt*otap t neu t rons d.

Deleved neutrons tal e longer to thermali e because they are born at higher energios than prompt neutrons OUESTION: 011 (1.00)

The reactor ic just critical at a low power level.

Which of the following is the stable reactor period resulting from the repid insertion of a rod with a reactivity worth of -0.003 delta K/K' a.

-30 seconds b.

-50 seconds c.

-80 seconds d.

-120 seconds

(**f**

CnfEGORY A CONTINUED UN HEXT PAGE 44244)

l i

A.

RX THEORY, THERMO & FAC OP CHARS Pope 9

I OUESTION: 010 (1.00)

Which one of the following is a benefit provided by photonautrons?

a.

Serve as a startup source, the eby removing the need for an external source b.

Contribute to Tritium production, thereby allowing detection of fuel lealage c.

Increase the effective core burnup. thereby provAding better fuel utilination d.

Increose the ratio of prompt to delayed neutrons, thereby increasing reactor control OUESTION: 013 (1.00)

Assuming the Samarium worth is 0.006 delta N/K at full power. which one of the following is the Samarlun, worth ten days af ter shutdown?

c.

Eccenticily zero b.

Essentially 0.006 delta K/V c.

Lesh thkh 0.006 delte K/K, but greator than zero d.

Greater than 0.006 delta K/K l

OUESTION: 014 (1.00)

Which one of the following is-the princips, source of best in the reactor j

after o shutdown f rom extended opera tion a t 2 MW7 a.

Delayed neutrons I

b.

Photo neutranc c.

Decey of core ec,mponen ts d.

Dtcay of fisalon productn

(*t4a* CATEGORY A CONTINUED ON NEAT PAGE $44**)

A.

RX THEORY. THERMO & FAC OP CHARS Page 10 QUESTION: 015 (1.00)

Whic h of the following are characteristics of a good moderator?

a.

Low seattering cross section end low abscrption cross pection b.

Lciw e,c e t teri ng c ros s sec t ion and high ebsorption ct oss-

'icChion c.

High vcettering cross cection and low absorption crous BOCtion d.

High ucattering cross section end high absorption cross section OUEST10N 016 (1.00)

Which one of the following in a correct statement concerning the f ac tor'A affectirg control rod worth 7 e.

As moder ator temperature increaser, control rod worth decreaseu b.

Fuel burnup causes the control rod worth for the periphery rods to decrease c.

Fuel bur nup causes the control rod worth for the rode in the center of the core to increase d.

The withdrawal of an adjacent rod causert the rod worth of the stationary control rod to increase i

(t*44t CATEGORY A CONTINUED ON NEXT PAGE tt9*4) l l

._,.-m.__.,

i i

t e

-i i

h i

O.

RX 1HEORY, THERMO & FAC OP CHARS Page 11 I

i i

I t

QUES 110N: 017 (1.00)

~;

i The reactor has been observed to jr

.ser from 15 Watts to 50 KW in 243 seconds.

Which one of-th:

4cwing is the stable reactor period I

which retoulted Je the power c hango',

I t

a.

10 ;ocond I

b.

30 uucond l

t.

202 Locond d

293 cecond I

r OUESTION: 018 (1.00)

A complete core reload is in p* ogress at UVAR.

The following data has been

(

taken.

Number of Elements Detector A (cpm)

Detector D (cpm) i Installed i

0 16

-20 i

12 22 32 l

24 29 37 l

.6 40 60 42 70 340~

.{

Using the inverce count rate.fAgure i provided, determine which one'of the following is the approximate number of fuel elements that will'tso required l

to bt-loaded for a critical mass.

I a.

45

-i i

ts.

50 it l

-c.

DD

)'

i i

d.

60 I

5 i

(14*$4 CA1EGORY A CONTINUED ON NEXT PAGE

  • 44**)

l

,._,__._._,,-.,_,....__..___..,.__'I

.-... - -. =. - - -.

A.

RX THEORY, THERMO h FAC OP CHARS Pogo 12 t

QUE5 TION: 019 (1.00)

Assume a moderator coefficient of reactivity equal to-2 EE-4 delta K/K/deg F with the reactor operating at 1 MW.

Which one of the following is the anioun t of regulating rod movement f or a nioderator temperature increase of 10 deg F7 a.

1 inch b.

2 inc het, c.

5 2nthes d.

10 inches 2

i

('

l (t4*4* END OF C AT EGOf?Y A 44444)

~ _ _... _.,,.

. _. -...... _.,.. _.,...... _ _. _.. _. _ _..... _. _,.... -....,,..., _ -. - _, _, ~.. -.. - _...... _. _..

- ~.

D.

NORMAL /EMERG PROCEDURES 4: RAD CON Page 1:

QUESTION: 001 (1.00)

A chutdown of the reactor by insortion a scram is planned.

Which one of the following IS NOT an acceptable method of inserting the neram in accordance with SOP 5.7.A. Reettor Snutdown?

o.

I nser t: ng e reactor period screm b.

Ut.tlitina-the I;oy switch on the conso.

c.

Deprunting the scram push button on-the console d.

Dupressing the Primary _ Pump Start puth button 1

OUESTION: 000 (1.00)

Which one of the following is the minimum delta K/K change that is defined as a change in core configuration in accordance with SOP 5.4, Core Menipulations?

a.

0.01%

l b.

O.1%

c.

0.5%

d.

0. 7 5'..

l (4441i CATEGORY D CONTINUED ON NEXT PAGE 44x4*)

_~.

D.

NORMAL /EMERG PROCEDURES & RAD CON Page 14 OUESTION: 003 (1.00)

When losding fuel, no reactor core shall be taken critical with shim rod positions below ten inchen and the regulating rod fully withdrawn.

Which one of the following is the basis for this restric tion in accordence with SDP 3.4.2.A, Loading Core from a Configuration which cannot be tal:en Criticel' a.

This escures that sufficient shutdown margin in available for the reactor to be shut down with the insertion of the shim rodu alone b.

This assures that the regulating rod will remain in the operating band

c..

This assures that shim and regulating rod positions at 100% power will maximi::e f uel burnup d.

Thib assures that the reactor will not go critical when pulling shim rods two at a timo dut'ing startup OUECTION: 004 (1.00)

The operator is going to remove two chim rods from the core.

Which one of tne following precautions must be taken prior to removing the shim rodw lei ectordance with SOP 5.3.2.D. Control Rod Handling?

a.

Remove two fuel elementu next to each shim rod to be removed b.

Remove four fuel elements from the centcr of the core c.

Remove two fuel elements from the cenier of the core d.

Remove one fuel element next to earh chim rod to be removed l

l l

l (t****

CATEGORY B CONTINUED ON NEXT PAGE 4**t4)

i t

t

[

D.

NORMAL /EMERG PROCEDURES & RAD CON Page IS

?

1

?

OUESTION: 005 (1.00)

Which one of the following defines "Menon free" conditions for the core in 1

eccordance with SOP 5.6, Procedure for Determining Xenon-free Conditionu?

i 1

I a.

Xenon warth 1est then G. i d e l t a l? /l..

t b.

Xenon worth less than 0.0S% delta t- /K i

c.

All the fuel an the reactor han not been at a power above i MW for the last 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> l

d.

All the f ue.1 in the reactor has not been operated at a power level 6

above 500 1:h in the lest 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> t

OUESTION: 006 (1.00)

During an inspection of the core at the 500 KW power level, air bubbles are observed on the core.

Which of the following methods should be used to remove the air bubbles in accordance With Abnormal Condition 11.1, Removal of Air Bubbles from the Core?

a.

Gradually increase power to i MW, observing the core to accure the air bubbles have been removed, t

b.

Reduce power to sub-critical, return to 500 KW and observe that the air bubbles have been removed-c.

Shutdown the reactor, observe that the air bubbles have been l

removed and call the cognizant senior operator

+

a d.

Shutdown the reactor, stop the primary pump and observe that the air bubbles have been removed I

t t

1 1

l l

t t

(t1144 CATEGORY B CONTINUf:D ON NEXT PAGE

$4***)

.~,

_..=.

_. ~---

s 4

)

B.

fiQRM%42 ERG PROCEDLLR.Es ? RAD COM Page 16 OUESTION: 007 (1.00)

Which statemen t below, regarding the release of pond water to Meadow Creek.

is correct in accordance with SOP 10.5 Reactor Facility Radioactive Waste Disposal' a.

The Reettor Supervisor and the On Duty SRO must approve all pond water releases.

b.

Ii the pond water reachus a level lesu than one foot below the i

top of the.r,p i l l w a y,

semple must be taken.

a i

c.

If pond water activity is greater than 3 EE-8 microcuries/mi. the i

water must be diluted prior to reicase.

d.

One week prior to discharge. three samples must be or&wn to determine pond water activity.

OUESTION: 000 (1.00)

Which one of the following amountu of radiation would be most damaging to the body' a.

A beta emitting point source of 0.5 mrad per hour on contact.

b.

An alpha emitting point source of 0.5 mrad per hour on con tac t.

c.

A gamma emitting point source of 10 mrad per hour on contact.

L d.

A fast neutron emitting point source of 10 mrad per hour on t

contact.

DUESTIONt 009 (1.00)

I A ten curie source is removed from the reactor after radiation.

It-emits a 2 Mov gamma.

Consider this a point source. and there is a two inch lead i

i shield at the source.

Which one of the following lu the minimum distance from the source an individual must be to avoid being in a high radiation crea:

f a.

6.5 feet b.

7.2 feet i

c.

10.9 feel I

l cl.

12.1 feet (ttt44 CATEGORY D CONfINUED ON NEX1 PAGE

  • 44**)

i

,.n--

4 D.

NORMAL /EMERG PROCEDURES & RAD CON Page 17 DUESTIONI 010 (1.00)

Which one of the following is a condition that requires a senior reactor operator's presence at the facility in accordance with SOP 3. Personnel Responsibilities?

a.

Planned shutdownc b.

Remuvel of en experiment of 0.2% delta L/E or greater f rc,m the reactor t.

Diotharging liquid to the waste porid d.

Recovery from a thutdown due to a spurious trip DLIESTION: Oli t'i.00)

Water needs to be released from the pond.

Analysis of the water indicates an activitv of S.O EE-7 microcuries/ml.

Which one of the following statements is correc t concerning the disposition of the water in the pond?

a.

The water may be releeced using the normal procedure since the release limit is 1.0 EE-6 microcuries/ml b.

The water may be released with dilution flow from city water to reduce the reactivity to 1.0 EE-7 microcuries/ml c.

The water may be released through a 50 micron filter as long as tn= set'."ity is less than 1.0 EE-6 microcut-ics/ml d.

The water cannot be re49ased since the release limit for waste weter is i.0 EE-7 mictocuries/ml DUESTION: 012 (1.00)

Which one of the following is the annLial administrative radiation exposure limit established by UVAR for operating personnel?

a,

'.125 rem / year b.

O.2D rem / year i

c.

0.50 rem / year d.

1.25 rem / year (ti444 CATEGORY El CONTINLIED ON NEXT PAGE 4****)

s i

D.

NORMAL /CMERO PROCEDURES & RAD CON Page 10 OUESTION: 013 (2.00)

For the instrumentation in Column I SELECT the Operating Mode from Column Il for which the instrumentetion is required to be operable according to Technical Specifications. (Items.tn Column 11 may be used once, more than once, or not at all.

A Single rosponwe will occupy each space on Column 1.)

COLUMN I COLUMN II

( I n s t. rumen t a t ion )

(Operational hade) e.

Pool Watet i

Forced Convection Level Monitor

_ _,b.

Pool Water 2

Natural Convection Temperature c.

Startup Count Rate 3

Reactor Startup d.

Reactor Period 4

All Modes (4 anrowers required at 0.5 each)

OUESTION: 014 (1.00)

During reactor power operation the RAD ZONE ENTRY" alarm is annunciated.

Which one of the following will initiate the alarm according to Abnormal Condition ii.C. Radiation Zone Entry Alarm?

a.

The electric eye r.ystem on the heat enchanger room l

b.

The entry alarm on the demineralizer room t

c.

The entry alarm to the large access facility d.

The eritry alarm to the " Rabbit" facility (1****

CATEGORY B CONTINUED ON NEXT PAGE 444**)

D.

NORMAL /EMERG PROCEDURES & RAD CON Page 19 QUESTION: 015 (1.00)

While operating at power, the MAGNE'i ENGAGED light for a shim rod goes out and the SEATING light becomes illuminated.

Which onn of the following actionk should be tel:en in accordance with Abnormal Co /ition 11.D, Dropped Rod (t)"

a.

Immediately scram the reactor b.

Fully irem er t the remaining shim rods and the regulating rod c.

I n t.e r t the remaining shim rods to ten (10) inches d.

Reengage the shim rod and obtain the senior operators permission to return it te its original position OUESTION: 016 (1.00)

A fueled esperiment which will generate a power of greater than one watt is to be irradiated.

Which one of the following requirements must be satisfied prior to the e<periment irradiation in accordance with SOP 6. Material Irradiction end Post Irradiation Handling?

a.

The e::perimen t must be in the reactor pool and under at least 20 feet of water b.

The thermal power generated in the experiment shcIl be i

limited to less than 10 watts c

The irradiation must be approved by the Reactor Health Physicist d.

The irrediation must be approved by the Reactor Safety Commi t tee I

I l

i 1

(4*4**-CATEGORY B CONTINUED ON ;JEXT PAGE v4444)

I i

1 i

i Ii B.

NORMAL /EMERG PROCEDURES ?: RAD CON Paqu 20 f

' l l

OUESTION: 017 (1.00)

\\

An emergency has occurred requiring the evacuation of the focility.

Which i

one of the following individuals (by title) is responsible for au t hori::ing -

j re-entry. int.o the facility, in accordance with the University of Virginia Restler Fecility Emergency Plan?

a.

Facility Director (Emergenty Director) i i

6 b.

Reactor Supervisor (Lmergency Coordinator) i I

c.

Director of Radiological Safety

!t d.

Health Physicist i

f l

OUESTION: 010 (1.00)

I

)

An ALERT emergency has been declared at the University of Virginia Reactor 5

Facility.

Which one of the following is the maximum amount of time allowed i

for notification of the NRC in accordance with EPIP-8, Notification of NRC7 l

I a.

15 minutes i

b.

"'O Minutes

+

c.

i hour l

d.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> i

4 I

(

- I

. t i

5

- f

-)

1

. t I

e f

i i

i s

(*t4*4 CATEGORY D COnlTINUED ON NEXi P4GE 1 Al i 4 )

I

-,,-o

.,-.. w m.m.

.-.,,-,-.r,.

y, a.y

.._.m..%,%,%.....-m w....,-..

,,,,,.my.,y~.-,,..,,--...s.r,,m.c.,,..

D.

NORMAL /EMERG PROCEDURES & RAD CON Prae 21 GUESTION: 019 (1.00)

A fuel cladding failure is indicated by increased fission product activity in the pool.

SELECT the action that should be tal.en to determine which fuel e l emen t ( r. ) is (are) lealing?

a.

Reduce reettor p e wte r to leus that i MW and monitor the pool for decreased ac ti v ity b.

Tale e sample above each element until the suspect fuel e l errien t ( s ) is (are) located, then shutdown the reactor.

c.

Bhutdown the reactor and t cd. e a tomple above each fuel element to determine which fuel elementts) is (ere) leal:ing d.

Increase pool compling frequency to 15 minutes, and chutdown the reactor 11 two successive samples increase in activity OUESTION: 000 (1.00)

An evacuation of the Reactor Facility hat been ini tia ted ered the evacuation alarm has been actuated from the UVAR control room.

Which one of the following locations provides o station for resettino the alarm?

a.

First Floor Hollway L.

Ground Floor Experimental Area CAVALIER Control Room d.

UVAR Control Room t

i44445 END OF CATEGORY B 44444)

~,... - _._

~ _ _..

_ _,. -.. _ _ -, -. _ -. _ _,. - -, _ _ ~

a 0

1 a

4 4

I L

C.

PLANT AND RAD MONITORING SYSTEMS P60e 02-i OUEETION: 001 (1.00)

Which one of the following describes the plate design 1or a " standard" fuel olement?

1 e.

10 1lat plates b.

10 curved plates c.

19 flat plates d.

1G curved plates OLIESTION: 000 (1.00)

Assume the UVAR is being operatect at 2 MW when a totel loss of p t <.. r (alt electricity) to the facility occurs.

Which one of.the following offacts result from the power failure?

a.

Reguleting rod fails in its present position.

b.

Ventilation exhaust duct doorb fail open c.

Pool mal:e up valve f ails open d.

Personnel access doors fail to close I

l l

l 1

414itt CA1EGORY C CONTlNUED ON NEXT PAGE.t*$t4)

.- _ _ _ _, _.. ~, ~ _

..........,. _ _..... _. _, _.. - _. _. ~..

~_

l k

6 i

C.

FLANT AND RAD MONITORING SYS1 CMS bage 22 I

t i

OUEST1ON: 003 (1.00)

The return line of the primary-water heat exchanger to the pool in directed by a 1 low diverter toward the wall that is the greatest distanco l

from the reactor.

Which one of the following is the reacon for thit flow t

diversion, j

[

s a.

Preventb thermelly induced power osncillations by preventing cooler Water from impinging on the fuel l

i b.

Minimi;*eu vibration of the core by preventing Water from eniting close to the reactor t

c.

Prevento thermal stratification by cauhing pool turbulence when deflecting off the wall e

i d.

Mini mi: en the Nitrogen 16 gamma activity at the Euriate of the

{

pool by providing better mining 9UESTION: 004 (i.00)

Which one of the following conditions will result from e short circuit in the Silicon Controller Rectifiers (SCR'n)-in the Solid State Relay modules?

i

}

e.

A short circuit in one SCR will result in current being supplied j

to the ancociated safety rod even 11 an unsafe input ih applied b.

A short carcuit in both.SCR,s will - result in current being supplied to the scram magnets even if an unsafe input is applied I

l --

c.

A short_ circuit in one SCR will result in all' safety rods

.i l

being scrammed j

i d.

A t.hort circuit in both SCR.s rectifiers Will result in all. safety f

rode being scrammed

'i I

l 4

i (444

  • CATEGORY C CONTINUED ON NEXT PAGE 144*t)-

~,.._.,..._---m'..

-. - - -- -~~

h C.

PLANT AND RAD MONITORING SYSTEMS Page 24 s

QUESTION: 005 (1.00)

Whit.b one of the following events will occur if the separate remote power me te-Jutput from power range Amplifier "P" short circuits?

a.

The separate remote power meter output fails downscale and all other outputs foil full scale b.

T hr. ceparate remote power meter output failt upscale and all other outputu fail downstale c.

All outputo from power range amplifier "P"

fail downscale d.

The teparate remote power meter output tails downstale with little change in al1 other outputs OUESTION: 006 (1.00)

Which one of the following ranges of nuclear instrumentation utill::es a compensated ion chamber as the neutron detection device?'

a.

Source range b.

Intermediate range c.

Power range t

d.

Linear power range OUCSTION: 007 (1.00) l Which one of the following statements. describes the drive speeds of the shim rods and the regulating rod?

j l

a.

The shim rods drive at 24 inches per minute while the regulating rod drives at 3.74 inches per minute b.

The chim rods drive at 3.74 inches per minute while.the reguleting rod drives at 24 inches per minute c.

Both the shim rods and the regulating rod drive at 3.74 inches per minuto d.

Both the shir rods and the regulating rod drive at 24 inches-per minute

(*****

CATEGORY C CONTINUED ON NEXT PAGE

        • t)

4 C.

PLANT AND RAD MONITORING SYSTEMS Page 25 OUESTION: 000 (i.00)

Four grooves are cut in each side of an absorbing section of a control rod.

Which one of the following is the design basis for the grooveu?

a.

Provide coolant flow channels to maintain minimum temperaturo increase in the rod during operation t>.

Allow for therms) enpansion of the rod during high pcwer operation c.

Minimize hydriding of the utainless steel due to prolonged exposure to primary coolant at elevated temperatures d.

To increase the surface area for the absorption of neutrono during power operation OUESTION: 009 (1.00) l Which one of the following fuel configur ations will provide the h.

hest neutron fluh in the core?

o.

A 4u4 array includina the four control rod assemblies with water as the reflec tor b.

A on4 array including the four control rod assembles with 40 graphite assembles surrounding the 4x4 array i

l c.

A 4x5 array including the four control rod assemblies with water as o reflector d.

A 4x5 array including the four control rod assemblies with 44 graphite assemblies surrounding the 4x5 array l

i l

i l

l l

i**44f CATEGORY C CONTINUED ON NEXT PAGE i.4444)

=

I j

-j i

C.

PLANT AND RAD MONITORING SYSTEMS Page 26 e

i OUESTION: 010 (1.00) 1 i

.l 1

The reactor _ room ventilation exhaust ducts have doors which become a part of the reac tor room isolation.

Which one of the following cescribes thtw mec han a t.m by which the ventilation exhaust doors are closed for a high l

re,d i a tion condition?

l T he doors are held open by a pneumatic cylinder which it v.

deprecsurized on high radiation 'in the ven tilation exhaust -duc t l

cloving the doors l

4 b.

The doors are held open by a solenoid operate muchanical _ latch which releasos the doors on high radiation detectett on -either of two constan t air monitorp i

{

c.

The doors are opened manually and held open by a magnet which releaces the doors on high radiation at the reactor bridge d.

The doort. are held open by ventilation air flow which is htopped by a trip of the ventilation fans on high radiation in the ventilation exhaust duct.

O ii OUESTION: 011 (1.00)

A-fueled onperiment is being irradiated in the reactor _ pool when a failuro l

of the experimen t releases fission byproducts.

By what detector would the release be detected and what automatic action would be initiated?

a.

Either of.two air monitoring instruments cente the fiction product release and provide automatic closure of the reacter_ room b.

A gamma sensitive ion chamber at the top of.- the reac tor pool provideo automatic closure of.the reactor room and a reactor trip on high gamma level c.

Either of two air monitoring instruments sense.the ficsich product release and provide a reettor trip d.

A gamma centitive ion chamber-at,the-top of the-pool provides Oh alarm.tn the control room if the radiation-exceeds the octpoin7 (t*4*t COTEGORY C CONTINUED ON NEXT PAGE 44i44) 1 f

e C.

PLANT AND RAD MONITORING SYSTEMS Page 27 d

OUEST l c' 012 (1.00)

=

Eeth of the ventilation ducts leading from the experimental facilities can be fitted with an internal radiation monitor.

Which one of the 'following describes the type and operotion of the monitor?

I a.

The instrument it a thin walled scintillation detector senultive to low levels of Beto Gemma radiation and atolateu the particular duct on a count rate of 800 cpm b.

The instrument is a thin walled scintillation detector sensitive to Beta radiatjan and alarms in the control room on a count rate of 100 epn abcoco background a

c.

The instrument it a thin walled G-M tube dotector sencitive to low level of Deta Gamma radiation and isolates the duct at 100 cpu above bactground d.

The anutrument in a thin walled G-M tube detector sensitive to Beta radiai. ion and alarms in the control room on a count. rate of 800 cps OUESTIONt 013 (1.00) 7he buildup of Argon 43 in the North Neutron Beamport has been minimized by p

e modification.

Which one of the following describes the method used to minim 2 :* e the Argon 41 buildup?

a.

A constant purge flow of cir is circulated h the beamport' during opergtlon and exhausted to the atack b.

The front tube is filled with demineralized water during operation to minimize neutron activation c.

A Baron Pcraffin sleeve surrounds the wtperament to be irradiated to minimi;:o the eir Ectivation

'd.

Whet i the front tube is drained J t as filled with Helium ges 611minating air-3cFivation in the tube

  • 1.444 t~ATEGORY C PONTINUED ON NEFI fl(EE i t t 4 *. )

o e

f C.

PLANT AND RAD MONITORING SYSTEMG Page 29 t

OUESTION: (.14 (1.00)

W51th one of the following correctly describes the operation of the temperature monitoring system for the UVAR reactor?

n.

1hu delta-T obtained from the temperature detectore on the inlet and the outlet of the heat exchanaer can be related to reactor ibcrmal power b.

An outlet temperature of 10S den F irom the heat cychanger Will initiate a reactor ucram c.

The de l t a--T ob tained from the pool temperature detector and the temperature dutec tor on the suction of the primary pump can be related to reactor power d.

A delta-T of OS deg F acroct; the core as detected by the temperature monitoring system Hill initiate a reactor scram OUESTION: 015 (1.'.iO)

Which one of the following is a description of the operation of the primary coolant headers e.

The header is raised and held in place at the reactor grid plate by a 50 psig air pressuro cylinder b.

The header is held in place by the differential pressure generated by primary coolant flowing down through the core i

t.

A trip of the Primary Pump de-energi:en en electro-megnet that holdn the head er in position, thereby e1 lowing the header to drop d.

Stopping the primary pump vents the air from the header operating system, thereby allowing the header to drop I

d t44444 c ATE GOPi C CONfINUED 00 NEM PAGE

  • 44**)

s

~

t C.

PLANT AND RAD MONITORING SYSTEMS Page 29 OLIEST I ON : 016 (1.00)

Wnich one of the following conditions will initiate a reactor scram if operating at 2 MW?

a.

Evacu a tion alarm h.

High red 2ation on the criticality monitor High del t o -T acros3 the tore t.

d.

Secondary pump deenergined NUESTION: 017 (l.On) i W uch one of the following descrioes the operation of the rod withdrawal in t ;r loci:'

a.

11 cource rar7e count rato drops below 2 counts per second (cps) the Auxilian Control Relay (ACR) output increases from ero to

+10 volts pieventing the withdrawal of any rod s

b.

A +10 volt signal is generated if any neutron monitoring channel tu in tes t', de-energining the regulating rod drive motor t.

A r mctor period of lors than 10 seconds de-energines the shim rod dr

' motors, preventing rod withdrawal d.

If source rangs count rate is less than 2 (cps). or any neutron monitoring channel is in test, withdrawal of any shim rod is prevented OUESTION; (1.00) a 6

Assuno ng a six inch water seal on the underwater escape ha tc h, which one of the following internal pressures would result in breakino the reactor building integrity?

a.

.127. psig I

b.

.222 psay c

. ? !. ! pulg I

1 -i ' pnia

\\

(t144t ERTEGORY C CONTINUED ON la T PAGE 4tt**'

Q.,3

?

.. =..

-6 g

t^

l C.

PLANT AND RAD MONITORING SYSTEMS Page 30 i

1 i

i t

C4UEST I ON : 019 (i.00) t Which one of the following statements describes the method for maintaininq the level and purity of the water in the Core Spray Emeroency Storage tanks?

\\

a.

The discharge of the primary coolant pump uupplies flow through a i

small line into the. tanks causing overflow in to the pocl b.

A smal1 flow of cily water into the tanks causen the tankc to overflow J"to-the pool c.

Cor evec tive tiow within the tanks prevents stagnation and minimines corrosion d.

Continuous flow through a discharge line from the demineraliter I

enters the tank causing a slight flow through the spra_y headeru 1

OUESTION: 020 (i.00) i Which one of the following is the only gaseous ef fluen t produced during power operation of the UVAR reactor?

a.

Argon 41

.I b.

Nitrogen 16 l

c.

Oxygen 18 t

d.

Iodine 131

?

I i

i r

1 i

4 i

F 1

J l

(.t :t t t t END OF LATEGORY C t*444)

(*4*r$>4+**

EttD OF EXAMINATION

    • t*******)

l

)

- -.. - -. ~ -. -. - -

n.

GA

't I tE0hY. ~IHEHMO F FAC f)F CHARS Page 71

~.

ANSWER:

001 (1.00) c.

REFERENCE:

Re ac i_ o r T h e o r ',' for the Reac tor Training Program 1940011(101

.. ( FA ' c )

ANSWER:

002 (1.00) c.

REFERENCE:

Reactor Theory for the Reactor Training Program 194001K102

..(KA'si ANSWER:

003 (1.00) d.

REFERENEE:

General Theory l

ANSWER.

004 (1.00) b.

REFERENCE:

DPC. pages 113/114 ANSWER 005 (1.00)

&4*t& CATEGO*O 4 CONTINtJED ON !iEXT PoOE ti<r&;

l n.

PX THEORN. TilERMO & FAC JP CHARS PMu

.2

REFERENCE:

Reactor Theory for the Reactor Training Program, Fission Product Poisoning 194001F:107

..(KA's)

ANSWER:

006 (1.00) c.

REFERENCE:

Reactor Theory for the Reactor Training Program ANSWER:

007 (1.00) d.

REFERENCE:

Reactor Theory for the Reactor Training Program ANSWER:

000 (1.00) c.

REFERENCE:

3 Lc, marsh Nuclear Recctor Theory Chapter 13.2 1

ANSWER:

009 (1.00) c.

REFERENCE:

I...e m a r s h Nuclesr Reactor Theory Chapter 13-2 1

ANSWER:

010 (1.00)

'4**ti bHhGURY A CUNTlNUED UN IC ! F N.m 4e14si

t 4

li.

R:( 'IHEORY, THERMO & FAC OF C H'4 R 3 Page 57

'EFERENCE:

Reactor theory for the Reactor Training Program 194001A112

..(FA s)

ANSWER:

011 l1.00)

C.

REFERENCE:

Rnactor Theory for the Reac tor Training Program ANSWER:

012 (1,00) a.

REFERENCE:

Lamarsh Nuclear Reactor Theory Neutron Producing Reac tions pp 67 ANSWER:

017 (1.00) d.

REFERENCE:

Renttor Theory 1or the f2eattar Training Programs AN AER:

014 (1.00) d.

REFERENCE:

Lamartih Nucleer Reactor Theory. Reactor Power pp 258 fi ISt iEP,

015 (1.00) t hihh 3"73 ' lI Y k..)

I I

fl l (

>l

(

3-y

._,y n,

4 e

n.

RA THEORY. THERMO ? PAC OP Cl uaRG Pago 3 'i

REFERENCE:

Lomorsh Nuclear Reactor Theory, Neutron Moderation with Absorption and Fission pp 218 ANSWEF:

O l e, t1.00) d.

REFERENCE:

Lome th Nuclear Reactor Theory. Section 14-1 Control Rod Worth pp 499 l

ANSWER:

017 (1.00) b REFEREt.CE :

l Reactor Theory for the Reactor Training Procram ANSWE7:

01 Et (1.00) y/ c;

REFERENCE:

Reacter Theor, for the Reactor ! r a in.t n g Program ANSWER:

019 (1.00)

/-

o PEFERENCE:

UVAk Denign a n ". ' An a l s u HanrJbook Table 3.1 pp 3-15

<-ttt

'.!!O Qi Cf.TEGURY itttt) i

4 I

D.

NORMAL /EMERG PROCEDURES ' RAD CON Paqu -~. 5 ANSWER:

001 (1.00) a.

REFERENCE:

LIVAR SOP 5 Step S.3.A.2 pp 5-U ANGWER:

002

( 1. 00 ) -

b.

REFERENCE:

UVAR SOP 5 Sec tion 5.4.1.1 pp 5-9 i

1 ANSWER:

003 (1.00) d.

REFERENCE:

UVAR SOP 5.4.2.A.1 pp 5-10 I

ANSWER:

004 (1.00) b.

REFERENCE:

UVAR-SOP 5.4.2.D.1.a pp 5-20 ANSWER:

005 (1.00)

REFERENCE:

UVnP OOP 5.6 op 5-24 tt*tt C, iT E'. H u 5.;OilTINUED ON NEX1 PfiGE tit *4)

~. -.

- -- -...~-

o i

.i 0

D.

NORMAL /EMERG PROCEDURES A RAD CCra Page.36 ANSWER:

006 (1.00) d.

REFERENCE:

UVAR SOP 11.I pp 11-10 ANSWER:

007 (1.00) c.

REFERENCE:

UVAR SOP 10.S pagen 10-9, 10 l

ANSWER:

000 (1.00) d.

REFERENCE:

10 CFR 20.5 ANSWER:

009 (1.00) l l

C.

REFERENCE:

General Theory.

ANSWER:

010 (1.00) d.

REFERENCE:

n-O P,.;. - 1 (4444* CATEGOPY D CONTINUED ON NEXT PAGE i4 t 4 t )

-. ~. - -........ -.. -, -, -

., ~, -

-.~ -..

l e

i o

D.

NORf%L/EMEPG PROCEDLIRES 0 RAD CON Fage "7

ANSWER:

011 (1.00) d.

REFERENCE:

UVAR Decicin and Analvnis Handbool:

Cection 4.0 pp 4-10 ANSWER:

012 (1.00) c.

REFERENCE:

UVAR Dossign and Analysis Handbook Section 7.5 pp 7-4 ANSWER:

013 (2.00) a.

1 b.

4 c.

3 d.

4 (4 answers required at-0.5 each)

REFERENCE:

i UVAR Technical Specifications Table 3.1 UVAR Design and Analysis Handbook Eec tion 3.7 pp O-36 ANSWER:

014 (1.00) b.

REFERENCE:

l U'>nn GOP 11.C.e.1 pp 11 4 l

l

.,.tiee csTesoav 1: cu n naico un te..

a 4 r 4 e +,

yr

,+e s-en-r y

=

,-e,.w

---Je 4e,qr

  • ,p-wwirv+

4

~. _

e e

D.

Il0P11AL /EMERG PPOCEDUf(E5 & PAD CON Page -* G ANEWER:

015 (1.00)

C.

REFEPENCE:

UVM Ahnormal Condition 11-D pp 11-5 ANSWER:

016 (1.00) d

REFERENCE:

UVAR SOP 6.1.B.7 pp 6-3 UVAR Technical Specification 0.7 pp 20 ANSWER:

017 (1.00) a.

REFERENCE:

University of Virginia Reactor Facility Emergency Plar. Section 3.2.2 pp 9 i

l ANSWER:

010 (1.00)

.c.

REFERENCE:

UVAR EPIP-8 Se_ tion 2.D pp i i

i l

ANSWE F, :

01v i1.00) c.

'Atit% CNIEGOR)

B CONIINUED ON HEi1 PAG ' & v i t i,.

l l

a e

6.

NORMAL /EMFRG PROCEDURES

!. RAD COM Page 7.9 REFEPENG:

UVAR EPIP-10 Section 2.f pp 3 ANSWER:

020 (1.00) d.

REFERENCE:

UVAR EPlP-14 Sec tion 3 pp 2 L

k 6

P i

(!*4**

Ef 4D OF CATEGOR/

I; 41(i*'

r i

l

u e

C.

PL(INT AND RAD MONITORING SYE'TEt15 Page 40 ANSWER:

001 (1.00) 0.^ Gl or 4

REFERENCE:

UVAR Destan and Analysis Hand bool:

Sec tion 1.2 pp 3-6 ANSWER:

002 (1.00) s.

REFERENCE:

UVAR Design and Analysis Handbook Sect 3.5 pg 3-9, Sect 6-1 pg 6-4 ANSWER:

003 (1.00) d.

REFERENCE:

UVAR Dec1gn and Analysis Handbook Section 4.5 pp 4-4 ANSWER:

004 (1.00) u.

REFERENCE:

1 l

UVAR Design and Analynis Handbool:

Section 3.6.6.1 pp 3-31 ANSWER:

005 (1.00) d.

l I

T E F E R E H C._ :

UVaR D e s.t an and Anal, cit Hendtrol.

Sec t. t on. 6. 4 pp 3-29

.*?tt L(a!E(,09:

4 L.ON I t huk D i.d ' NEX1 T'f6 C i6++t;

C C.

PLANT.AND RAD MONITORING SYSTEMS Pace 41 1

ANSWER:

006 (1.00) d b.

or

REFERENCE:

UVAR Design and Analysis Handbool:

section 3.6.1 pp 3-19 to 21 ANSWER:

007 (1.00) t b.

REFERENCE:

UVAR Design and Analysis Handbook Section 3.5 pp 3-16 ANSWER:

000 (1.00) i d.

REFERENCE:

,~

UVAR Design and Analysis Handbook Section 3.5 pp 3-9 I

ANoWER:

009 (1.00) i b.

t

REFERENCE:

i-I UVAR Design and Analisis Handbook Sec tion 3.3 pp 3-6, 3-9 ANSWER:

01.0 (1.00) 4 c.

REFERENCE:

I MV< Design and,:n -.1 T t r Handbook Bection 6.1 pp 6-4 3

'4i*

_J, ! E b O R 's C CUNTINUED C'ti NEXT PACE 4tttt) a O

J.

,_,,y,--,w,,.,--w.,,.

..,-_c.

-,y

,._m.-3

._y.,%

y.,,

,,...y...

,7.,, _,,,...,... ~. < -,.,,,, _,,,,,,,,...,, _ _

og,.,w.w4.y y.-E e 4

,,,.,,,,, _ - +

i i

L C.

PLortT AND RriD MONITORING SYSTEMS Page 42 AMSWER:

Oil (1.00) b.

REFERENCE:

UVAR Design and Ar.e l yt ic Hand bool: Section 5.4.2 pp 5.S.

6 ANSWER:

012 (1.00) d.

REFERENCE:

UVAR Design and Analysis Handbook Section 4.9.4 pp 4-19, 20 ANSWER:

013 (1.00) d.

REFERENCE:

UVAR Design and Analysis Handbook Sec tion 4.9.3.4 pp 18, 19 i

ANSWER:

014 (1.00) c.

FEFERENCE:

UVAR Design and Analysis Hant 5 col:

Section 4.4 pp 4-4, 4-5 ANSWER:

01S (1.00) b.

REFERENCE:

NAR D:;1gn 2nd A n _ l ',- r i t Han d bool; Section 4.!

pp 4-2 (r<4 C,' T E G O R.

C COMTINUE!4 t+i ! 1-l. X,1 i%OE iA6tt)

.. ~.

d m

b C.

PLANT AND RAD MONITORING SYSTEMS Page 43 ANSWER:

016 (1.00) e.

REFERENCE:

UVAR Design and Analysis Handbool:

tiection 3.7 pp 3-36, 38 ANSWER:

017 (1.00) d.

REFERENCE:

UVAR Design and Analysis Handbool:

Section 3.6.6.4 pp 3-32 ANSWER:

010 (1.00)

W ck

REFERENCE:

UVAR Design and Analysis Handbook Section 6.'1 pp 6-1 ANSWER:

019 (1.00) d.

REFERENCE:

UVAR Design and Analysis Handbook Section 4.10 pp 4-28 ANSWER:

020 (1.00) 4\\.

REFERENCE:

UVAR Design and Analytis Handbool:

Section 4.9,1 pp 4-11

( 4441t END OF ZmL60RY C tittt)

(KJA6*v434t Ef tb OF LfANINATION Y414%)vtt*!

l

- ~.. - -.. -. -.

.,

Retrieved from "https://kanterella.com/w/index.php?title=ML20070S139&oldid=4420340"